ML20135B192
| ML20135B192 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/26/1996 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20135B176 | List: |
| References | |
| NUDOCS 9612040199 | |
| Download: ML20135B192 (27) | |
Text
{{#Wiki_filter:! a g. l Attachment I to JPN-96-051 PROPOSED TECHNICAL SPECIFICATION CHANGES (JPTS-96-001) i i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 9612040199 961126 PDR ADOCK 05000333 P PDR =
JAFNPP e G. 0 TABLE OF CONTENTS (Cont'd) Eage F. ECCS-Cold Condition F. 122 G. Maintenance of Filled Discharge Pipe G. 122a H. Average Planar Linear Heat Generation Rate H. 123 (APLHGR) 1. Unear Heat Generation Rate (LHGR)- 1. 124 J. Thermal Hydraulic Stability J. 124a SURVEILLANCE ' LlMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.6 - Reactor Coolant System 4.6 136 A. Pressurization and Thermal Limits A. 136 B. DELETED C. Coolant Chemistry C. 139 D. Coolant Leakage D. 141 E. Safety and Safety / Relief Valves E. 142a F. Structural integrity F. 144 G. Jet Pumps G. 144 H. DELETED l. DELETED l 3.7 Containment Systems 4.7 165 A. Primary Containment A. 165 B. Standby Gas Treatment System B. 181 C. Secondary Containment C. 184 D. Primary Containment Isolation Valves D. 185 3.8 Miscellaneous Radioactive Material Sources 4.8 214 3.9 Auxiliary Electrical Systems 4.9 215 A. Normal and Reserve AC Power Systems A. 215 B. Emergency AC Power System B. 216 C. Diese! Fuel C. 218 D. Diesel-Generator Operability D. 220 E. Station Batteries E. 221 F. LPCI MOV Independent Power Supplies F. 222a G. Reactor Protection System Electrical Protection G. 222c Assemblies ~ 3.10 Core Alterations 4.10 227 A. Refueling Interlocks A. 227 B. Core Monitonng B. 230 C. Spent Fuel Storage Pool Water Level C. 231 D. Control Rod and Control Rod Drive Maintenance D. 231 3.11 Additional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventilation A. 237 B. DELETED C. Battery,' loom Ventilation C. 239 Amendment No. M-0Br440,1SS,231 li
(. JAFNPP LIST O.F TABLES Iable Iit!e Eage 4.2-8 Minimum Test and Calibration Frequentj Accident Monitoring 86 Instrumentation i 4.6-1 (DELETED) 161 I I_ 4.6-2 Minimum Test and Calibration Frequency for Drywell Continuous 162a l Atmosphere Radioactivity Monitoring System ~4.7-1 (DELETED) 210 l 4.7-2 (DELETED) 211 3.12-1 (DELETED) 244a 3.12-2 (DELETED) 244a l 3.12-3 (DELETED) 244a" l-4.12-1 (DELETED) 244a l l 4.12-2 (DELETED) 244a 4.12-3 (DELETED) 244a 6.2-1 Minimum Shift Manning Requirements 260a 6.10-1 Component Cyclic or Transient Umits 261 i I i-l Amendment No. 90, 22, 02, 144r400r464r450r+78-180r48h410r248r284 vi i i = - - ~ -., _
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1 JAFNPP l 1 l } } Pages 161 - 162 DELETED l i i 4 1 i l 1 l i Amendment No. 96,-480, 161
1 JAFNPP (B) The following records shall be retained for the duration of the Facility Operating License: 1. Records of any drawing changes reflecting facility design modifications made to systems and i equipment described in the Final Safety Analysis Report. 2. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. 3. Records of facility radiation and contamination surveys. 4. Records of radiation exposure for all individuals entering radiation control areas. 5. Records of gaseous and liquid radioactive material released to the environs. 6. Records of transient or operational cycles for those facility components identified in Table 6.10-1. 7. Records of training and qualification for current members of the plant staff. 8. Records of in-service in.spections performed pursuant to these Technical Specifications. i 9. Records of Quality Assurance activities required by the Quality Assurance Manual.
- 10. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- 11. Records of meetings of the PORC and the SRC.
- 12. Records for Environmental Qualification which are covered under the provisions of paragraph 6.15.
j
- 13. DELETED I
6.11 RADIATION PROTECTION PROGRAM i Procedures for personnel radiation protection shall be prepared and adhered to for all plant operations. These procedures shall be formulated to maintain radiation exposures received during operation and maintenance as far below the limits specified in 10 CFR 20 as practicable. The procedures shall include planning, preparation, and training for operation and maintenance activities. They shall also include exposure allocation, radiation and contamination control techniques, and final debriefing. i Amendment No. 22, 37, 02, Ordc dated Octcbcr 24,1000 255
e Attachment ll to JPN-96-051 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES (JPTS-96-001) i i i l i 1 i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
... -. -. -. - - - - _.. _ - -. ~... - i Attachm3nt ll to JPN-96-051 i i. SAFETY EVALUATION t 'e Page 1 of 6 i 3 1. DESCRIPTION OF THE PROPOSED CHANGES This section provides a description of the proposed changes to the Technical i Specifications (TS). Minor changes in format, such as type font, margins or hyphenation, are not described in this submittal. This type of change is typographical in nature and i does not affect the content of the TS. 1 li DESCRIPTION OF THE PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS { l This amendment proposes to relocate snubber testing requirements from the TS to the ISI program. Inghnical Soecifications Pace li. Table of contents i Replace the following: I "l. Shock Suppressors (snubbers) 1. 145b" l with "l. DELETED" Technical Soecifications Pace vi. List of Tables l Replace the following: i i "4.6-1 Snubber Visual Inspection Interval" with "4.6-1 (DELETED)" Technical Soecifications Paoes 145b through 145g Delete Pages 145b through 145g Technical Soecifications Pace 156 Replace the text in Bases Section 3.6.1 and 4.6.1 with the following: "l. (DELETED)" ' Technical Soecifications Page 156a Delete Page 156a Technical Soecifications Paoes 161 throuah 162 Replace Pages 161 through 162 with a new Page 161, which will state: "Pages 161 - 162 DELETED"
. 1 to JPN-96-051 SAFETY EVALUATION Page 2 of 6 Technical Soecifications Page 255 Replace the following: "13. Records of the service life of all hydraulic and mechanical snubbers, whose failure could adversely affect any safety-related system, including the date at which the service life commences and associated installation and maintenance records as of J the effective date of this amendment." with "13. DELETED" ) 11. PURPOSE OF THE PROPOSED CHANGES The purpose of these proposed changes is to relocate snubber operability, surveillance, l and record requirements from the TS to plant controlled documents. The proposed change regarding the relocation of the surveillance requirements would facilitate changes needed to conform with NRC imposed ASME Boiler & Pressure Vessel Code requirements for the next ten year Inservice inspection (ISI) program which commences on June 28, 1997. NRC regulations (10 CFR 50.55a(g)) requim the ISI program to conform to the latest edition and addenda of the NRC approved Code in effect 12 months prior to the start of the ten year interval. This requirement invokes the ASME B & PV Code, Section i i XI,1989 Edition, for the next FitzPatrick ten year ISI interval. This code invokes the i snubber surveillance requirements of standard OMa-1988, Part 4. The snubber i surveillance requirements in this standard conflict with the current TS requirements (section 4.0.l). Approval of the proposed change will permit changes to the ISI surveillance program, under the provisions of 10 CFR 50.59, that recognize the NRC imposed Code requirements. Current plans are to locate the snubber surveillance requirements in the ISI program. Additionally, the amendment proposes to relocate the snubber operability and record requirements from the TS to plant controlled procedures. This change establishes uniformity with the administrative controls, and TS simplification change, proposed above for the surveillance requirements. Current plans are to relocate the snubber operability and record requirements to a plant administrative procedure. These proposed changes are based on the guidance presented in NUREG-1433 (Reference 1), NEDO-31466 (Reference 2), and the criteria presented in NRC regulation 10 CFR 50.36, and are consistent with NRC and industry efforts to simplify the TS. Revisions to the snubber requirements located outside the TS will be controlled in accordance with the provisions of 10 CFR 50.59, and will conform to the applicable NRC approved edition of the Code. Relief requests wiil be submitted to the NRC for approval if exceptions to code requirements are necessary. If snubber inoperability causes a TS system or component to be inoperable, then the affected system or component Limiting Condition for Operation (LCO) will be entered. The plant controlled documents associated with the relocated requirements will be referenced in the first FSAR update due more than six months after NRC issuance of the amendment. NUREG-1433 (Reference 1) This NUREG contains the improved Standard Technical Specifications (STS) for General
.~ Attachment ll to JPN-96-051 SAFETY EVALUATION Page 3 of 6 Electric (GE) BWR/4 plants. The Preface in this NUREG states that Licensees are encouraged to upgrade their Technical Specifications to conform with NUREG-1433. Operability, surveillance, and records requirements for snubbers are not included in NUREG-1433. 4 NEDO-31466 (Reference 2) This document concludes, in part, that snubbers do not need to be retained in TS. The following excerpt from this document forms the basis for this conclusion: " Hydraulic and mechanical snubbers are included in plant design to ensure that the structuralintegrity of the reactor coolant system and other safety-related systems are maintained during and following a seismic or other dynamic loading event. The snubbers are considered a part of the piping system. They serve as an aid to preventing piping failure, but do not mitigate piping failure. Also, the failure of a snubber on a particularpipe cannot, by itself, cause the pipe to fail. Consequently, the snubbers do not meet any of \\ the criteria since they are not utilized as a part of the primary success path in detecting or j mitigating the consequences of a DBA or transient event. Additionally, the surveillance l and maintenance of the snubbers can be controlled by sources other than the plant Technical Specifications." Code of Federal Reaulations.10 CFR 50.36 (Reference 3) NRC regulation'10 CFR 50.36, as amended on August 18,1995, identifies the criteria to 1 be used in determining whether a particular system or component is required to be included in the TS. Existing TS requirements which fall within or satisfy these criteria must be retained in the TS, while those TS requirements which do not fall within or satisfy these j criteria may be relocated to other licensee-controlled documents. The snubber requirements FitzPatrick TS Section 3.6.1/ 4.6.1 do not satisfy the selection criteria in 10 CFR 50.36 for inclusion in the TS since they (1) are not used for detecting a significant abnormal degradation of the reactor coolant pressure boundary, (2) are not an initial condition of a DBA or transient analysis that either assumes the failure of or 1 presents a challenge to the integrity of a fission product barrier, (3) are not part of the primary success path and do not function or actuate to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity or a fission product barrier, and (4) do not involve a component for which operating experience or probabilistic safety assessment has shown to be significant to public health and safety. Therefore, the requirements for snubbers can be relocated to plant controlled documents. Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES There are no safety implications associated with these changes because: if snubber inoperability causes a TS system or component to be inoperable, then the affected system or component Limiting Condition for Operation (LCO) in the TS will be entered. Regulations and FitzPatrick commitments to the NRC contain the J necessary programmatic requirements for plant controlled documents. 4 the provisions of 10 CFR 50.59 apply to changes made in the plant controlled documents to assure the changes do not involve an unreviewed safety question. The snubber surveillances will conform to NRC approved Codes, unless specific relief is requested from the NRC.
Attachm:nt il to JPN-96-051 SAFETY EVALUATION Page 4 of 6 i these proposed changes were developed using the guidance contained in NUREG-1433 (Reference 1), NEDO-31466 (Reference 2), and N7C regulation 10 CFR 50.36 (Reference 3), and are consistent with NRC and iredustry efforts to simplify the TS. Operating limitations will continue to be imposed, and required surveillances will continue to be performed in accordance with regulations, Fitzpatrick commitments to the NRC, and written procedures and instructions that are auditable by the NRC. Since the proposed amendment only involves the procedures for controlling the snubber requirements, and j does not involve changes to the operability and surveillance provisions in the snubber program, the proposed changes are administrative in nature and will not reduce the effectiveness of the snubber program. IV. EVALUATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment will not involve a significant hazards consideration as defined in 10 CFR 50.92, based on the following: (1) These changes do not involve a significant increase in the probabl!ity or consequences of an accident previously evaluated because: The changes relocate operability, surveillance, and record requirements for components (snubbers) which do not meet the criteria for inclusion in the Technical Specifications (TS). The affected components are not assumed to be initiators of analyzed events and are not assumed to mitigate accident or transient events. The snubber requirements will be relocated from the TS to plant controlled documents. These requirements will be maintained pursuant to 10 CFR 50.59. Therefore, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. (2) The changes do not create the possibility of a new or different type of accident previously evaluated because: The changes do not necessitate a physical alteration of the plant (no new or different type of equipment will be installed) or affect parameters governing normal plant operation. Adequate control of future changes to snubber requirements will be maintained. Thus, these changes do not create the possibility of a new or different kind of accident from any accident previously evaluate for the plant. (3) The proposed changes do not involve a reduction in a margin of safety because: The changes do not involve a change to the operability, surveillance, and record requirements for the snubber program as they currently exist in the TS, nor do they impact on any safety analysis assumptions. The proposed changes relocate snubber requirements from the TS to plant controlled documents. Changes to the requirements in these documents are subject to the requirements of 10 CFR 50.59. In addition, exceptions to code requirements for testing will require NRC approval. Regulations and FitzPatrick commitments to the NRC contain the necessary programmatic requirements for the plant controlled documents. Operating limitations will continue to be imposed, and required surveillances will continue to
' 1 to JPN-96-051 SAFETY EVALUATION Page 5 of 6 be performed in accordance with regulations, Fitzpatrick commitments to the NRC, and written procedures and instructions that are auditable by the NRC. If snubber inoperability causes a TS system or component to be inoperable, then the affected system or component Limiting Condition for Operation (LCO) will be entered. Based on the above, the proposed changes do not involve a significant reduction in i a margin of safety. j V. IMPLEMENTATION OF THE PROPOSED CHANGES This amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) as follows: (i) the amendment involves no significant hazards consideration. As demonstrated in Section IV of this evaluation, the proposed change involves no j significant hazards consideration. (ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed changes do not involve a physical alteration to the plant, or any ) changes in plant operating procedures. The proposed changes are administrative j in nature in that they relocate the snubber operability, surveillance, and record requirements from the TS to plant controlled procedures. Future changes to the these documents are subject to NRC regulations. Therefore, these changes do not i change the amounts of any effluents that may be released offsite. (iii) there is no significant increase in individual or cumulative occupational radiation exposure. The proposed changes do not alter plant operating or surveillance procedures, and therefore will not change individual or cumulative occupational radiation exposure. i Based on the above, it is concluded that there will be no impact on the environment resulting from the proposed changes and the proposed changes meet the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to requiring a specific environmental assessment by the Commission. Additionally, implementation of the proposed changes will not adversely alter or affect the ALARA program or the Fire Protection Program. VI. CONCLUSION Based on the discussion above, the snubber operability, surveillance, and record, requirements can be relocated from the FitzPatrick TS to plant controlled documents. If snubber inoperability causes a TS system or component to be inoperable, then the affected system or component Limiting Condition for Operation (LCO) will be entered. The PORC and SRC have reviewed these proposed changes to the TS and have concluded that the changes do not involve an Unreviewed Safety Question, or a Significant Hazards Consideration as defined in 10 CFR 50.92, and do not endanger the health and safety of the public.
Attachment il to JPN-96-051 SAFETY EVALUATION Page 6 of 6 I- - Vll. REFERENCES 1. NUREG-1433, Standard Technical Specifications, General Electric Plants, BWR/4, Revision 1, dated April 1995 2. NEDO-31466, Technical Specification Screening Criteria Application and Risk Assessment, dated November 1987 l 3. Code of Federal Regulations, Title 10, Part 50, Paragraph 50.36, Technical Specifications. 9 a a en e
s 11 to JPN-96-051 MARKUP OF TECHNICAL SPECIFICATION PAGES (JPTS-96-001) NOTE 1: Deletions are shown in strikcout, and additions are in bold. NOTE 2: Previous amendment revision bars are not shown, l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
JAFNPP i a IABLE OF CONTENTS (Cont'd) Eage i F. ECCS-Cold Condition F. 122 . l G. Maintenance of Filled Discharge Pipe G. 122a H. . Average Planar Unear Heat Generation Rate H. 123 (APLHGR) 1. Unear Heat Generation Rate (LHGR) I, 124 J. Thermal Hydraulic Stability J. 124a SURVEILLANCE l LIMITING CONDITIONS FOR OPERATION REQUIREMENTS - 3.6 Reactor Coolant System 4.6 136 A. Pressurization and Thermal Umits A. 136 B. DELETED C. Coolant Chemistry C. 139 D. Coolant Leakage D. 141 E. Safety and Safety / Relief Valves E. 142a F. Structuralintegrity F. 144 G. Jet Pumps G. 144 H. DELETED 1. DELETED Shock Suppressors-(Snt.bSers}- h 445b 3.7. Containment Systems 4.7 165 A. Primary Containment A. 165 B. Standby Gas Treatment System B. 181 C. Secondary Containment C. 184 D. Primary Containment Isolation Valves D. 185 3.8 Miscellaneous Radioactive Material Sources 4.8 214 . 3.9 Auxiliary Electrical Systems 4.9 215 i A. ' Normal and Reserve AC Power Systems A. 215 B. Emergency AC Power System B. 216 C. Diesel Fuel C. 218 D. Diesel-Generator Operability D. 220 E. Station Batteries E. 221 F. LPCI MOV Independent Power Supplies F. 222a G. Reactor Protection System Electrical Protection G. 222c Assemblies 3.10 Core Alterations 4.10 227 A. Refueling Interlocks A. 227 8. Core Monitoring B. 230 C. Spent Fuel Storage Pool Water Level C. 231 D. Control Rod and Control Rod Drive Maintenance D. 231 3.11 Additional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventilation A. 237 B. DELETED C. Battery Room Ventilation C. 239 4 Amendment No. 20, 43, 08, 113,-1687231 il
i JAFNPP i e LlST_QF_ TABLES I 1 2 Iable lit!G Page l t 4.2-8 Minimum Test and Calibration Frequency for Accident Monitoring 86 l .l Instrumentation 4 l i l 4.6-1 (DELETED) Snubber Visua! lnspection Interval 161 l 4.6-2 Minimum Test and Calibration Frequency for Drywell Continuous 162a Atmosphere Radioactivity Monitoring System i 4.7 1 (DELETED) 210 i 4.7 2 (DELETED) 211 1 3.12-1 (DELETED) 244a l 3.12-2 (DELETED) 244a 3.12-3 (DELETED) 244a l l 4.12-1 (DELETED) 244a l l-4.12-2 (DELETED) ' 244a 1 4.12-3 . (DELETED) 244a i 6.2-1 Minimum Shift Manning Requirements 260a l i 6.10-1 Component Cyclic or Transient Limits 261 l i i l I .i Amendment No. 20r22792r4447-480r464r160r476,-480r484re10rE4BrG34 4 vi i 1 \\
JAFNPP 84-{ cont'd) 44-{contM) 8.6.' ShocieSuppressors-{ Snubbers) 4.S.! ' Shoek4uppressors-{ Snubbers) apphCability 6pokeebtlity Appites404he-operationaHitatus-of-the-shoclesuppressors Apphes-lethe-penedtedesting-feguirement-for-the-shock (snubbers): suppressors-(snubbers): Obteetive Otxeetive To-assure 4he-capabilityef 4he-snubbers-to! Teessure4he-capabtlity ef4he-snubbers-to-perfonn4 heir intended 4 unctions: Preventenrestrainedppe-motionender-dynamte4oads as-mighteccurderingen-earthquakeer-severe 4ranstent; and Allow-normal 4hermal-motierHiuring-startup-and shutdown-Soecificatino Specificati00 Each-snubbershall4)e&monstrated-operable-by-performance of-the4ellowmgWervice-inspection-program: 4. During-all-modes-of+perationexcept-Gold-Shutdown 4. Allhhall4)e-categorized-inte-two-groups:-those andBefueling,-ell-snubbers-which-ere-required 40-proteet-accessible-and-those-enaccessible-during-reactor-the-pnmety-coolant-systemer-eny--other-safety + elated operation-Tievisual-enspection-interval 4er+acheategory system-or-component-shelf-be-operable-Ouring-Gold of-snubthbe-determined-basedepon4he-criteria Shtf.down-or-Refuehng-modeof-operation;-only4 hose provtded-in-Teb!c 4.S 1 snubbenHshalf-beeperable-whtehereeneystems4 hat-are-required 40-be-operable-in4hese-modes: Amendment 440-20, 02, 08-480 445b
~ O JAFNPP BE-(cont'd) 4-6-{ cont'd) 2. With-one-or-more-snubtwrs-enoperable;-within-72-hours 2. Visuehnspection sha!! verify (Q4hebthere-ere-no-visible during-normel-operation or-withen-7-daye-dunrwyGold-indiestions-of-demage-or-tmpaired-OPERABIL4'Pfr(2)- r Shutdowner-Refueling modeof-operation-for-systems atteehrnents404hMoundettoner-supportingstructure-ere wtvehere-required 40-beeperabletn4heseinodes; securerend-(B}-in4 hose 4ocettons-where-snubber-complete-meef4he4enowimy movement thoutdtseonnecting the-snubber thebthesnubber-has-freedom-of-movement r e--repieceer-restore 4he4noperable-snubber (s)-to ends-not4rozernap-Snubbers-which-sppeer-moperabless operable-statuser; e-resulbef visuallnspections-may-be-detemuned OP Efi ABLE4er-the-purposeef-establishtng4he-next-visual b. declare 4hesupported systenanoperableend4ellow inspection 4nterveirproviding4het-{4 Fthe-eeuseef-the theeppropriate4imitingeondition4or-operation rejectioras-c! car!y established-en4+emed+ed-for-that statement 4or-theFsystem-or; particuler-snubber-end4er-ether-snubbers-that-may-be-genenca!!y susceptibierend-(2)4he-effectedsnubber-is c. perfommengineenngevaluation40-show4he functioneHy-tested 4n4hess-found-condition-and-inoperablesnubber-is-unnecessary-toessure determined OPERABLE per-Specifications 4.S.! 7 or-443B; operability +Fthesystem-or4o-meeFthe-design-es-eppiteab!c. Hydraulichhave-losF eriferieef4he-system mdfemove4hesnubber-from suffietent4iuid-to-potentially-cause uncovenngef4he-fluid-r the system-reservoir-to-snubber-valve assemblyportor4xMtomingef the-hteteservoir-piston-with4he-snubber-in4he4uHy extendedpostteen-sheH-be4unctionally4ested40-determine-operability: 3. Witheneer-more-snubbers 40und moperabiervnthen-72 3. Once-every-2+ months;-10%ef-eeeh4ype-of-snubbers-sheH hours-perform-e-visual 4nspectionef4he-supported-be4unctiona!!y tested 4er-operabilityreither-in-pieceer-in-e component (s}-esseetated-with4heanoperable-snubber (s) bench 4est-For-eachentbendsubsequenbuntt4habdoes and<focumenFthe-results-For-elFmodes-of-operation-noFmeeFthe-requiremcats-of 4.6.! 7 cr 4.S.I.6, aa-edditianel excepFGold-Shutdownend-Refuelingr ithin44-days 40Wof4 hat 4ypeef-snubber-sheH-be-functioneHy tested-until w comp!cte an engmeenng-evaluation-es-per-Specifiestion n&fnere failurcs arc foundrer-eH-units 4mve-teen 4ested: 46.F6-to-ensufethat4he-tnoperablesnubber(s}-has-not adverselyeffected4he-supportedeomponent(s}-For-Gote Shutdown cr Refuc!ing-moderthis evaluation-shalFbe completed-within-8G<1ays-AmendmenFNo. 20, 02, 08,14BrtBGr226 445e
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n u -2_-_a T, h,,:-. - -o m m.'.g g eu.. ~. -m m e m o. .:.-_ mm,. un u :ma --. ru ms m..m .m_ . _ -.h i a E UMm. w s. ru s t ou suru uw se ruwpu us st m t v s w qo.u m, a rw. rt .-A mk .- sm. -~.Lu _ mm.:..-. u s,.. M.: .u-t.mm. osum w uuv.h am osuv uww.o arvi. s evu tu y .n su u L,Vs i suos a...u. ru. ubbbys ui Nw us nu t, t 6-Fc..u. ~ ..uus. g,s s~o.nd-moperebi, u, r _rgmeermg .~ mm v ~. m _.._i....: nu m. u.m.. u. u.u.. performed <m.,u, ~ ___, e. om.,ym ~,.. suppo.au...u.~ .uusa,. r,,u ~. _ _ o H hts .. u o, e,~ mms 3 ~ yo,ruem engineenng evaluation sha!! belo<!ctermine if the [ ooryu..ma u.,..u ,~.uusa,....- udversely compm,. - . ~... .mu m.. ~ e muum uo ...m eff. 7ted4ry the inoperetsty-cf the Ont;bber{s}* order 4e ens. ki .us u.v voyy m suu uvii y m ui..-._ _ _: _._-a_._ t so. u...u. meeting 4he-desi, cd-service--requerements-3 r l t t i + v i. f i ) e I, ? i. i AmendmentWo. 02.08,100 445e 1 - - - - - - - - =
s.. JAFNPP ~ I. 8-6-{ cont'd) WC0f4D) 7 The-hydraulte-snubber-functional test sha!! verify that; a. ^ctivetton (rcstrainingeetion) is achieved withen4he specified-fange of vc!cetty-cr accc'crettoran-bot tenston and compresston-b. c~.m. w..-d-c.. i_---._., h, ere-+eqwredr is a
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.vithin the specified rsmterston-For snubbefsepectitca':y required +10t-to-displace under-continuous 40ed,-the ability of-thesnubber4e v.ithstand -be verified: h 8. 30 mcchenical snubber 4unettonal test shell-venfy4het-a. The4erce4hatriticic^ free-mover 4entef the-snubber rod 4netther tensioner-compressim. is ! css then4he specified maximum drag 40ree-Dieg-force-shell-not have increased 4nere4 hen 50% sir:c+the4est t funettonal test. S spectfted+ange-of-velocity +r-neeeleratiorHn both tenstonendempression-s k l Amendment-No. 02, OS 445f ? t
o ale JAFNPP B.6-(contd) 4:6icent'd) c. Snubber-re! case raterwhere+equired,-+s-within4he specified+ange-ecompresstoner4enston-For snubbers-spectftcally-required-noHo-dtsptace-ender continuous 4ead, the cbility-of-lie-snubber 40-withstand lead-withoutifisplacementshalbbe-verified: D. Saubber-Service Life '/onitoring A-record +f4he-service !!!c of-eachenubber whose4ailure r could-adversely affect-the-pnmaryixdenter-other safety-relatedeystem the-datest-wtuch4he-designated r servicedifetommencesrend4he-tnstallationend maintenance +ecords<nwhich4he-designatedservice4ife-is basedshalFbeinatntatnedes-required-by-specification 6.40.B40: Once-every 24 rnenthsrthe4nstallation-andinaintenance recordsr4er-each-snubber whose4ailuree.fid adversely r eHect4he-pnmarysocianter-ether-safety +elatedsystemt shalFbereviewed40-verify 4habthe-+ndteated-service 4ifehas not een-exceeded cr veill nobbe-exceeded-pnor-to4he-next scheduledsnubber-servtec life revicv.. If-the-endteated service !!!c icill be-exceeded-pner404he-nextscheduled snubber-servtec life revieve the-snubber-service life shalFbe r reevalucteder4he-snubber-shall-be+eplaceder reconditioned-so-es4eextend4tseervice4ife-beyond4he-date of4he-r=exFscheduleservice !!!c revicv. This-reevaluation; replacementor+econditiontng-shalbbe-endteated4n4he records-AmendmentWo. 02,98,226 145g
D 4 JAFNPP 3.6 and 4.6 BASES (cont'd) supporte4eomponent(s)-assectate4wittHhe-tnoperablesnubber(s) ' and4he results-shell-be-documented. For a!! modesef+peration-except-Gol46hutdownend Refuc!!ngrwithen-14-daysen H. (DELETED) engineenngevaluat6eensure4 hat 4he enoperable-snubber (s)4ms-not-edversely affecteethe-supported I. (DELETED) component (s}-FoFGol6 Shutdown-or-refueltng moderthis Shock-Suooressers evaluatNthin-80-days. A penodof-7-days has-bcen sc!ccted-for-repatr+r-repleeement-of4he-inoperable Snubbers-are-destgnedte prevent-unrestratneeptpe-motion snubber-dunng-coldshutdewrver refuc!ing-modedoperation-undeedynamieloads-es-might-occur 4unng-ervearthquake because4n4hese-modes 4he-relative-probabtlity-of-structural or-severe 4ransientrwivle-ellowing+iormel-thermelanotton damagelo4he-pipingsystems-would-be !crect duelo4ower-values dunngstartupendshutdown-The-consequeneeef-en of40tal-stresses-ordthetiping systems-irkcasc a shutdown-es inoperable-snubber is arvincrease irtthe-probability-of required-the-allowanco of SS hours 4e+each ecold-shutdown structural-damage 40 piping-ese+esult-of-eSeismie-or-conditiordwilipermit-anerderly-shutdown-consistent-witivstandard other-event-tnitiating4ynamte4oads-iHs-therefere-fequired operating-procedures-that-atsnubbers-required to-proteet4hepnmary-coolant-systemeFany-otheesafety-system-or-component-be The-visuaHnspectiordfrequency-ts-baseo--uponinaintaining-a operable-dunng+eactor-operation-Snubbers exclude 4from constant !cvc! of snubber-protection 40eystems--Therefererthe-inis-inspectionprograntere4 hose-installeden -non-safety requiredanspection-intervahvaries-inversely v/itivtheebserved relatedeystemend4hervonly-if-4heiefailureer4ailure-of4he snubberleilures-end-es-determinedby4he-number-of-enoperable systemen-whteh-they-are4nstalledwoulehave-na-adverse snubbers fouiWton-inspeettons-performed-before-effectervenysafety-relatedeystem-Because4he-snubber that-mtervaHms-elapse 4may be-used as a new+eference-point 40 protection 4s+equtred-only -duringlowprobability-eventsre determine 4hesext-inspection-Thesnspections-ere performed-4er pened of 72 hours-(for-normal-operation}-or-7-days-(for eeetvealegoryef-snubbers-The-snubbers-ere-categorized 43y col 4 shutdown-oFrefueltng mode-of-operation)-is-eilowed4er accessibility-(i-e-accessible-oFtnaccesstble-during-feactor-repairs-or-feplaeement-of-the-snubber-pner4o4aking-any operation)--The-next visual inspection for cacticategory-may-be other-eetton-Following4he-72-houe(or 7 day)-penodrthe tweeerthesameror-feduce4by-as-muettes4wo-thirds-of4he-supportedsystem-musFbe-declaredinoperable-and4he previous inspection-intervat--Thes-interva! depends-on4he-number Limiting-Gonditionel-OperatiordstatemenFfor-the-supported of-unacceptab!c snubbers 4cund-trvproportiordto4twHotal-number system 4010wed-As-en-eltemativelo-snubbeerepaiFor of-snubbers 8 replacement-ervengineeringevaluettervinarbe-performe4-to-shovelhat4heinoperablesnubber is unnecessary 40 assure operability +f4he-system-or40-meet 4he-design eriteriaef4he-system-endrto-remove 4he-snubbeFfrorTHhe-systern--With-eneeFmore-snubbers 40und-tnoperable; within-72-hours-a-visual-inspectiordshall-beperforme4on the Amendrnent No. 20792r98-148-480 156
) JAFNPP ') e Pagts 161 - 162 DELETED n 4 TeL41 ,A c4 m .u Snubber-VisuaHnsoeciton4nterval Number-ef4fnacceptable-Saubbers i Golumn-A3 Column # ColunnG' Populetton" Extcaded Repeat Reduce i Gategory intersal interval Interval i l 4 A A 4 s v v s O A._ p A r3 vv v v s. l -400 0 1 4 _.4rn n n o W L# u u 1 m e 4n i s. m.s uo k 1 ,300 5 12 25 l u_.~.. 4 Tu,. __,..: m.,.i : _,~ :~, :_.__._i<~ .u_.,~,..i_.:~._,,, ~...u m ~..~.__.a_i, 1 vutu s. u. s I ru u avat v sowuu 11 vayvuuv1i ri stuu v u. e vi u rv yvyvius.vu i vi u ai ruuvwi uuswyvu y ai rurs 1 a _. _ _ :,,, M, u..m_. .u_ fu v.:m._svua rs sgyvuuvs a su nw s yus ur vu si vu u vui s sung vi vyvu a as rv m
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i.._ ,m, vi us.u - me m ble ~ ,, m ro.u..v um.. ~ I ruru.u... m 3v. on m ru o m u snubbm__1.- __:_:ble. -Tt,ro,., ~,., i m.~ . x,. i: _ :.,, ~,_ em....... m-m.. ru im3 ,v um. uium vi um,i s,,, ,v Gol M m, D,, A,, u, ru_ii u_..,.-a *f4 hat :.~.~ :~m.i.. des-a-ffacitoi.u,. mi.o. mv of A i uu u,mo t I,uu3m.i ru .u s. ..~,u,m__m..,.mi_ _ mbbe~i, ue us u,, s..~mo my i,..~. poletton- _ -. a _. __ : u u.. :. vi emum e, s .m 3. lHhe-number of unacceptab'c snubbers is cauaHo or ! css thaa4he-number 4n Golumnethe-nexHnspection-interva! may-be4wtee4he-previous 4ntervat-but-not greater 4han 48 months-4--4Hhe-number-ohinacceptable-snubbers is cauaHo-orless-thandhe-number-in Golumn S but-greater-than4he-number-in-Golumnethenext-inspection 4ntervaf-shell be4hc same as4he-previous 4ntervah Amendment No. 96r480 161
I JAFNPP e
- [ N Tab!c 4E 1 foont'd) b Snubber-VisuaHnsoeotion4ntefval
\\ 5:---4f4her. umber of-tinacceptableMinubbers is equal 40er-greater than the number 4neolumn Gr4het.cxt inspection 4ntervefdalFbe4wo4hirds of the previousanterva!. However, if the number-ofWeble-enubbers is ! css thandhemumber4n Column C but greater than the-number-trtBolumne,4te-next4ntervatshalFbe+ educed-by-e4 actor 4 hat 4sene4tirdef the4etio of the dtfierenee-between4hemumber+fmnacceptable-snubbers !cund during4he previous latervaFend4hemumberinGolumn44o4heefference4n4he-numbers-m GolumnsesndEr: I 1 l l i i i f '6 I' i-t i i l l 4 d#vh AMMaw% Anh kkA. M 4M r u i IUi tui s svi n iiv vu, ivu 462 l l l l I i I i l
i JAFNPP , 4 4 (B) The folicwing records shall be retained for the duration of the Facility Opesating License: 1. Records of any drawing changes reflecting facility design modifications made to systems and l equipment described in the Final S6ty Analysis Report. l l 2. Records of new and irradiated fuel inventory, flel transfers and assembly burnup histories. 3. Records of facility radiation and contamination surveys. 4. Records of radiation exposure for all individuals entering radiation control areas. l S. Records of gaseous and liquid radioactive material released to the environs. l 6. Records of transient or operational cycles for those facility components identified in Table 6.10-1. 7. Records of training and qualification for current members of the plant staff. l 8. Records of in-service inspections performed pursuant to these Technical Specifications. 9. Records of Quality Assurance activities required by the Quality Assurance Manual.
- 10. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CfR 50.59.
- 11. Records of meetings of the PORC and the SRC.
- 12. Records for Environmental Qualification which are covered under the provisions of paragraph 6.15.
j l i
- 13. DELETED Records-oHhe-service 4ife-of-albhydrauliesnd-mechanical-snubbersr hose-failuretould w
adversely-effeet-eny-safety-related-system,-including-the-date-et-which the service life j commences-sndessociated-installation-and-maintenaneeseeords-es+f-the-effeetive-date-of this-emendment-(L11 RADIATION PROTECTION PROGRAM I Procedures for personnel radiation protection shall be prepared and adhered to for all plant operations. These procedures shall be formulated to maintain radiation exposures received l during operation and maintenance as far below the limits specified in 10 CFR 20 as practicable. The procedures shall include planning, preparation, and training for operation and maintenance activities. They shall also include exposure allocation, radiation and contamination control techniques, and final debriefing. l l Amendment No. 22r37 92 7 Order 4ated@etober 24,1980 255 f I
i [ y#4 Attachment IV to JPN-96-051 James A. FitzPatrick Nuclear Power Plant List of Commitments i Number Commitment Due Date JPN-96-051-01 Relocate snubber operability, surveillance, Ninety days (90) after TS and record requirements from the TS to amendment is issued by the plant controlled documents. NRC JPN-96-051-02 Reference the plant controlled documents First FSAR update due more associated with this TS amendment in the than six months after NRC FSAR. issues amendment. !}}